| Development and optimization of STEP—a linear plasma device for plasma-material interaction studies GH Lu, L Cheng, K Arshad, Y Yuan, J Wang, S Qin, Y Zhang, K Zhu, ... Fusion Science and Technology 71 (2), 177-186, 2017 | 56 | 2017 |
| Gas-and plasma-driven hydrogen permeation through a reduced activation ferritic steel alloy F82H H Zhou, Y Hirooka, N Ashikawa, T Muroga, A Sagara Journal of Nuclear Materials 455 (1-3), 470-474, 2014 | 50 | 2014 |
| Deuterium gas-driven permeation and subsequent retention in rolled tungsten foils F Liu, H Zhou, XC Li, Y Xu, Z An, H Mao, W Xing, Q Hou, GN Luo Journal of Nuclear Materials 455 (1-3), 248-252, 2014 | 45 | 2014 |
| Studies on oxidation and deuterium permeation behavior of a low temperature α-Al2O3-forming FeCrAl ferritic steel YP Xu, SX Zhao, F Liu, XC Li, MZ Zhao, J Wang, T Lu, SH Hong, HS Zhou, ... Journal of Nuclear Materials 477, 257-262, 2016 | 43 | 2016 |
| Overview of plasma–material interaction experiments on EAST employing MAPES F Ding, GN Luo, RA Pitts, A Litnovsky, X Gong, R Ding, H Mao, H Zhou, ... Journal of nuclear materials 455 (1-3), 710-716, 2014 | 34 | 2014 |
| Influence of He ions irradiation on the deuterium permeation and retention behavior in the CLF-1 steel YP Xu, T Lu, XC Li, F Liu, HD Liu, J Wang, ZQ An, F Ding, SH Hong, ... Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2016 | 30 | 2016 |
| Comparison of tritium release behavior in Li2TiO3 and promising core-shell Li2TiO3–Li4SiO4 biphasic ceramic pebbles Q Qi, J Wang, Q Zhou, Y Zhang, M Zhao, S Gu, M Nakata, H Zhou, Y Oya, ... Journal of Nuclear Materials 539, 152330, 2020 | 28 | 2020 |
| Deuterium permeation and retention in copper alloys HS Zhou, HD Liu, ZQ An, B Li, YP Xu, F Liu, MZ Zhao, Q Xu, F Ding, ... Journal of Nuclear Materials 493, 398-403, 2017 | 27 | 2017 |
| Atomistic study of hydrogen behavior around dislocations in α iron T Lu, YP Xu, XD Pan, HS Zhou, F Ding, Z Yang, GJ Niu, GN Luo, XC Li, ... Journal of Nuclear Materials 510, 219-228, 2018 | 26 | 2018 |
| Hydrogen plasma-driven permeation through a reduced activation ferritic steel alloy F82H H Zhou, Y Hirooka, N Ashikawa, T Muroga, A Sagara Fusion Science and Technology 63 (1T), 361-363, 2013 | 25 | 2013 |
| Fluence dependence of helium ion irradiation effects on the microstructure and mechanical properties of tungsten M Zhao, F Liu, Z Yang, Q Xu, F Ding, X Li, H Zhou, GN Luo Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2018 | 24 | 2018 |
| Molecular dynamics study of the diffusion properties of H in Fe with point defects T Lu, GJ Niu, Y Xu, J Wang, Z An, H Liu, H Zhou, F Ding, GN Luo, XC Li Fusion Engineering and Design 113, 340-345, 2016 | 23 | 2016 |
| The effects of irradiation and high temperature on chemical states in Li2TiO3 S Gu, B Ji, Q Qi, J Wang, H Zhou, Y Zhang, G Luo International Journal of Hydrogen Energy 44 (60), 32151-32157, 2019 | 22 | 2019 |
| Plasma-and gas-driven hydrogen isotope permeation through the first wall of a magnetic fusion power reactor Y Hirooka, H Zhou, N Ashikawa, T Muroga, A Sagara Fusion Science and Technology 64 (2), 345-350, 2013 | 21 | 2013 |
| Global gas balance and influence of atomic hydrogen irradiation on the wall inventory in steady-state operation of QUEST tokamak A Kuzmin, H Zushi, I Takagi, SK Sharma, A Rusinov, Y Inoue, Y Hirooka, ... Journal of Nuclear Materials 463, 1087-1090, 2015 | 20 | 2015 |
| Effects of surface conditions on the plasma-driven permeation behavior through a ferritic steel alloy observed in VEHICLE-1 and QUEST H Zhou, Y Hirooka, H Zushi, A Kuzmin, N Ashikawa, T Muroga, A Sagara Journal of Nuclear Materials 463, 1066-1070, 2015 | 20 | 2015 |
| R&D issues of W/Cu divertor for EAST Q Li, P Qi, HS Zhou, YY Zhang, ZS Yang, J Wu, GN Luo, JG Li, ... Fusion engineering and design 85 (7-9), 1106-1112, 2010 | 18 | 2010 |
| Mechanical strength stability of tritium breeding materials under high temperature deuterium conditions S Gu, Q Qi, Y Zhang, B Ji, H Zhou, GN Luo Ceramics International 46 (1), 1195-1202, 2020 | 17 | 2020 |
| A tritium permeation ‘short cut’for plasma-facing components of fusion reactors HS Zhou, HD Liu, L Wang, X Yang, Y Oya, MZ Zhao, T Tanabe, YP Xu, ... Nuclear Fusion 59 (1), 014003, 2018 | 16 | 2018 |
| A review on the development of the structural materials of the fusion blanket YP Xu, Y Lyu, H Zhou, G Luo Mater Rev A 32 (9), 2897, 2018 | 16 | 2018 |
